ML20050D592

Preliminary Evaluation of PWR Safety & Relief Valve Test Program Results,Point Beach Nuclear Plant. One Oversize Drawing Encl.Aperture Card Is Available in PDR

ML20050D592
Person / Time
Site:	Point Beach
Issue date:	03/31/1982
From:	EDS NUCLEAR, INC.
To:
Shared Package
ML20050D577	List: ML20050D576 ML20050D592
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM NUDOCS 8204120346
Download: ML20050D592 (9)

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PRELIMINARY EVALUATION OF PWR SAFETY AND RELIEF VALVE TEST PROGRAM RESULTS POINT BEACH NUCLEAR _ PLANT Prepared for:

Wisconsin Electric Power Company March 1982 i

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l 8204120346 820408

) PDR ADOCK 05000266 P PDR L

WISCONSIN ET,ECTRIC PRET,IMINARY EVALUATION POINT BEACII NUCT. EAR PLANT Page 1 of 8

1.0 INTRODUCTION

This report summarizes the preliminary evaluation of the capability of the Point Beach Nuclear Pla n t (PBNP), Units 1 and 2, cafety and relief valves to operate under expected operating and accident conditions. This preliminary evaluation is based upon a review of the results obtained by the Generic PWR Safety and Relief Valve Test Program, implemented by the Electric Power Research Institute (EPRI) at the request of participating PWR Utilities.

2.0 SYSTEM DESCRIPTION PBNP consists of two nuclear steam supply systems and two turbine generators; i.e. it is a two-unit power plant. Each unit is a pressurized water reactor system with two primary coolant loops, supplied by Westinghouse Electric Corporation. Each NSSS is rated at 1518 MW thermal. In general, Unit 2 is a mirror image of Unit 1.

The safety and relief valve system for each unit consists of:

o Two spring-loaded, Crosby Valve and Gage Co.

IIB-BP-86 series safety valves o Two Copes-Vulcan Inc. power-operated relief valves o Two Velan gate-type block valves with Limitorque operators I

l o Three pressurizer outlet piping lines: one j line, including a loop seal, for each of the l

two safety valves, and one (branching) line l for the block and power-operated relief valves l

i o A common discharge piping line, terminating in I

the pressurizer relief tank

WISCONSIN ELECTRIC PRELIMINARY EVALUATION POINT BEACil NUCLEAR P L A N' '

Page 2 of 8 An isometric <irawing of the safety and relief valve system for PBNP U it 1 is attached hereto (EDS Nuclear Drawing No. PBNP-S RV-01) . This drawing represents the as-built Unit 1 piping, as confirmed by the Wisconsin Electric program for NRC IE Bulletin 79-14. ' 'h e Un i t 2 piping layout is essentially a mir:or image Jwith slightly different supports 2: a Unit 2 drawing is not attached hereto.

Detailed parameters for the valves and piping are given in Tables 1, 2, 3, and 4.

3.0 PRELIMINARY EVALUATION 3.1 Applicability of EPRI Test Data Safety Valves - PBNP has Crosby ifB-BP-86, 4 K2 6 safety valves with loop seal inlet piping configurations. The EPRI Test Program included Crosby 6M6 and 3K6 safety valves with loop seals.

The Crosby safety valve test results are contained in Sections 3.4 and 3.5 of the EPRI Safety And Relief Valve Test Report. The 6M6 and 3K6 valves l are structurally and functionally similar to the 4 K2 6, and their test results are applicable.

i l Relief Valves - PBNP has four (two per unit) l Copes-Vulcan relief valves. One of the PBNP valves is essentially identical to a valve included in the EPRI Test Program. The only difference between the i

three remaining PBNP relief valves and the test valve is in the valve body size (two-inch diameter at PBNP). This difference would have no significant effect on the test data. The applicable test data is contained in Section 4.7 of the EPRI Safety And Relief Valve Test Report.

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WISCONSIN ELECTRIC PRELIMINARY EVALUATION POINT BEACli NUCLEAR PLANT Page 3 of 8 Test Conditions - the EPRI Test Program covers a range of fluid conditions chosen to effectively envelop those that must be considered for the PWR plants within the program. These include inlet fluid conditions of saturated steam, 150 degrees F water followed by saturated steam, saturated water, saturated steam followed by saturated water, subcooled (550 degrees F) water, and saturated steam followed by subcooled water. Backpressures to 650 psia have been used.

Preliminary review indicates that these testing conditions effectively envelop those which must be considered for PBNP.

3.2 Summary of Valve Test Results Safety Valves - the Crosby 6M6 and 3K6 safety valves generally operated successfully on saturated steam and saturated water, exhibiting rapid lift and stable behavior. In all cases they have functioned to relieve pressure and prevent excessive over-pressurization. Ilowever, during testing of valves with loop seals or with subcooled water at the valve inlet, valve chatter did occur on the test piping configuration. While this induced high-frequency pressure oscillations in the piping upstream of the valve, these oscillations did not appear to substantially affect either piping integrity or subsequent valve performance. Also, in some tests, full lift was delayed until the loop seal had cleared the valve. Again, subsequent valve performance did not appear to be substantially affected, and the valves functioned to relieve pressure and prevent overpressurization.

WISCONSIN FLECTRIC PRELIMINARY EVALUATION POINT BEACil NUCLEAR PLANT Page 4 of 8 Relief Valves - A Copes-Vulcan 17-4Pli relief valve was extensively teited at the Marshall and Wyle test facilities. Durinj the Marbsall test (steam only),

two sets of valve internals were utilized. While the valves did not always fully close, the maximum reported leakage was less than 0.8 gpm. At the Wyle facility, the valv3 was tested on both steam and water and the maxi aum reported leakage (for eight tests) was less than 0.08 gpm. These test results demonstrate the acceptability of the PBNP relief valves.

3.3 Conclusions The preliminary data reviewed to date indicate that the PBNP safety and relief valves will operate under expected NSSS operating and accident conditions.

Wisconsin Electric and EDS Nuclear are proceeding with the required detailed analyses. The results of this effort will be the subject of a future submittal.

g o a WISCONSIN ELECTRIC PRELIMINAFY EVALUATION POINT HEACll NUCLEAR PLANT Page 5 of 8 TABLE 1: SAFETY VALVE PARAMETERS, UNITS 1 AND 2 o Number of Valves (per unit) 2 o Manufacturer Crosby Valve and Gaje Co.

o Type Spring-loaded nozzle type relief valve o Designation: Size 4 K2 6 Style HB-BP-86 Type E Weight 520 lbs.

o Steam Flow Capacity 288,000 lbs./hr. (sat. steam)

(rated and maximum)

Inlet Outlet o Design Pressure and 2485 psig 500 psig Temperature 650 F 470 F o Valve Procurement Westinghouse G-676279, Specification (original) Specification 3.7.2, Rev. 1 l

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WISCONSIN ELECTRIC PRELIMINARY EVALUATION POINT BEAf 11 NUCLEAR PLANT Page 6 of 8 TABLE 2: PELIEF AND BLOCK VALVE PARAMETERS, UNITS 1 AND 2 o Nunber of Valves (per unit) Relief: 2 Block: 2 o Mar uf acturer Relief: Copes-Vulcan Inc.

Block: Velan o Type Relief: Globe Valves Block: Gate Valves o Steam Flow (Relief Valves) 210,000 lbs ./hr . (max) 179,000 lbs./hr . (normal) o Design Pressure and 2485 psig/650 F Temperature (Relief and Block Valves) o Set Pressure (Relief Valves) 2335 psig

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4 WISCONSIN ELECTRIL PRELIMINARY EVALUATION POINT BEACH NUCLEAR PLANT Page 7 of 8 TABLE 3: SAFETY-RELATED SEISMICALLY-DESIGNED PRESSURIZER OUTI.ET PIPING, UNITS 1 AND 2 .

O Pressure and Operating Design Temperature

- Unit 1: 2235 psig/653 F 2485 psig/680*F Lines #RC-250lR-2

1. RC-250lR-3

. - Unit 2: 2235 psig/653*F 2485 psig/680 F Lines #RC-250lR-2

1. RC-250lR-3 i

o Piping Supports Numbers Type

! - Unit 1:

(Line #RC-250lR-2) HS-14 Snubber RC-14 Spring Hanger RC-15 Spring Hanger RC-16 Spring Hanger

- Unit 2:

4 (Line # RC-250lR-2) HS-28 Snubber (2)'

RC-15 Spring Hanger RC-13 Spring Hanger 2S-266 Rigid Hanger RC-14 Spring Hanger 1

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WISCONSIN ELECTRIC PRELIMINARY EVALUATION i POINT BEAC NUCLEAR PLANT i

i Page 8 of 8 TABLE 4: pISCllARGE PIPING INFORMATION, UNITS 1 AND 2 o Pressure and Operating (max.) Design Temperature Unit 1:

(Lin: #RC-60lR-1) 497 psig/468*F 540 psig/477'F (Line #RC-60lR-2) 497 psig/468*F 540 psig/477*F Unit 2:

(Line #RC-601R-1) 497 psig/468* F 540 psig/ 477*F (Line # RC-60lR-2) 497 psig/468*F 540 psig/ 477 F o Piping Supports Number Type Unit 1:

(Line #SC-60lR-1) RS-200 Restraint HS-17 Snubber RC-17 Spring Hanger (Line #RC-60lR-2) HS-18 Snubber RC-12 Spring Hanger HS-200 Snubber S-248 Restraint RC-13 Spring Hanger H-200 Rigid Hanger RC-13A Spring Hanger RC-18 Spring Hanger S-247 Restraint Unit 2:

(Line #RC-60lR-1) H-201 Restraint HS-30 Snubber RC-10 Spring Hanger (Line # RC-60lR-2) HS-29 Snubber i RC.-ll Spring Hanger HS-1 Snubber 2S-265 Restraint RC-12 Spring Hanger H-200 Restraint .

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